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Master Curve analysis of potentially inhomogeneous materials

Engineering fracture mechanics, 2012-11, Vol.94, p.56-70

Scibetta, M.

2012

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Effect of prior crack growth on cleavage fracture of low toughness precracked Charpy specimens

Journal of nuclear materials, 2010-11, Vol.406 (1), p.113-118

Scibetta, M.

2010

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A cleavage fracture framework: New perspectives in cleavage modeling of ferritic steels

Engineering fracture mechanics, 2016-07, Vol.160, p.147-169

Scibetta, M.

2016

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Young’s modulus anisotropy in reactor pressure vessel cladding

Journal of nuclear materials, 2012-02, Vol.421 (1), p.172-175

2012

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Community Detection as a Tool for District Metered Areas Identification

Procedia engineering, 2014, Vol.70, p.1518-1523

2014

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Applying the Master Curve approach to a JRQ A533B Cl.1 material as part of the surveillance program of two BWR Units

Engineering fracture mechanics, 2014-03, Vol.119, p.97-115

2014

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Cost-Effective Precracking of Charpy V-Notch Specimens for Fracture-Toughness Testing Using a Piezoelectric Actuator

Journal of testing and evaluation, 2017-07, Vol.45 (4), p.1476-1483

2017

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Numerical simulations to support the normalization data reduction technique

Engineering fracture mechanics, 2006-03, Vol.73 (4), p.524-534

2006

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Experimental determination of creep properties of Beryllium irradiated to relevant fusion power reactor doses

Journal of nuclear materials, 2007-08, Vol.367, p.1063-1068

2007

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Characterisation of the fracture properties in the ductile to brittle transition region of the weld material of a reactor pressure vessel

Journal of nuclear materials, 2011-04, Vol.411 (1), p.25-40

2011

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Tensile properties and internal friction study of dislocation movement in iron–copper system as a function of copper precipitation

Journal of nuclear materials, 2007-05, Vol.362 (2-3), p.283-286

2007

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On the use of the crack tip opening angle parameter to explain the ductile crack growth behavior of miniature compact specimens

Engineering fracture mechanics, 2008-07, Vol.75 (11), p.3599-3610

2008

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Validation and application of the Master Curve and reconstitution techniques to a Spanish nuclear vessel

Engineering fracture mechanics, 2009-11, Vol.76 (16), p.2495-2511

2009

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Effect of prior crack growth on cleavage fracture of low toughness precracked Charpy specimens: FP6 IP PERFECT Project: Prediction of Irradiation Damage Effects in Reactor Components

Journal of nuclear materials, 2010, Vol.406 (1), p.113-118

SCIBETTA, M

2010

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Measurement of the Young modulus anisotropy of a reactor pressure vessel cladding

Journal of nuclear materials, 2008-01, Vol.372 (2), p.249-255

2008

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Improved safety margins for Belgian nuclear power plants by the application of the Master Curve approach to RPV surveillance materials

The International journal of pressure vessels and piping, 2007-09, Vol.84 (9), p.536-544

2007

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Structural integrity assessment of a nuclear vessel with FITNET FFS and Master Curve approach

Engineering failure analysis, 2010, Vol.17 (1), p.259-269

2010

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Analysis of tensile and fracture toughness results on irradiated molybdenum alloys, TZM and Mo–5%Re

Journal of nuclear materials, 2000-12, Vol.283-287, p.455-460

2000

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Instrumented hardness testing using a flat punch

The International journal of pressure vessels and piping, 2003-06, Vol.80 (6), p.345-349

2003

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Understanding of Tensile Test Results on Small Size Specimens of Certified Reference Material BCR-661

Journal of testing and evaluation, 2017-03, Vol.45 (2), p.20150377

2017

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Towards Crack Arrest Testing Using Miniature Specimens

Journal of ASTM International, 2009, Vol.5 (9), p.101002

2009

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Tensile and low-cycle fatigue properties of solution annealed type 316L stainless steel plate and TIG-weld exposed to 5 dpa at low-temperature (42°C)

Journal of nuclear materials, 2000-12, Vol.283-287, p.428-434

2000

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Analysis of the geometry dependence of fracture toughness at cracking initiation by comparison of circumferentially cracked round bars and SENB tests on Copper

International journal of fracture, 2000-06, Vol.103 (3), p.205-225

2000

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Reconstitution techniques qualification and evaluation to study ageing phenomena of nuclear pressure vessel materials (RESQUE)

Nuclear engineering and design, 2001-11, Vol.209 (1), p.67-77

2001

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SCK·CEN contribution to the IAEA Round Robin exercise on WWER-440 RPV weld material: irradiation, annealing and re-embrittlement

The International journal of pressure vessels and piping, 2002-08, Vol.79 (8), p.665-684

2002

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Master Curve analysis of potentially inhomogeneous materials

Effect of prior crack growth on cleavage fracture of low toughness precracked Charpy specimens

A cleavage fracture framework: New perspectives in cleavage modeling of ferritic steels

Young’s modulus anisotropy in reactor pressure vessel cladding

Community Detection as a Tool for District Metered Areas Identification

Applying the Master Curve approach to a JRQ A533B Cl.1 material as part of the surveillance program of two BWR Units

Cost-Effective Precracking of Charpy V-Notch Specimens for Fracture-Toughness Testing Using a Piezoelectric Actuator

Numerical simulations to support the normalization data reduction technique

Experimental determination of creep properties of Beryllium irradiated to relevant fusion power reactor doses

Characterisation of the fracture properties in the ductile to brittle transition region of the weld material of a reactor pressure vessel

Tensile properties and internal friction study of dislocation movement in iron–copper system as a function of copper precipitation

On the use of the crack tip opening angle parameter to explain the ductile crack growth behavior of miniature compact specimens

Validation and application of the Master Curve and reconstitution techniques to a Spanish nuclear vessel

Effect of prior crack growth on cleavage fracture of low toughness precracked Charpy specimens: FP6 IP PERFECT Project: Prediction of Irradiation Damage Effects in Reactor Components

Measurement of the Young modulus anisotropy of a reactor pressure vessel cladding

Improved safety margins for Belgian nuclear power plants by the application of the Master Curve approach to RPV surveillance materials

Structural integrity assessment of a nuclear vessel with FITNET FFS and Master Curve approach

Analysis of tensile and fracture toughness results on irradiated molybdenum alloys, TZM and Mo–5%Re

Instrumented hardness testing using a flat punch

Understanding of Tensile Test Results on Small Size Specimens of Certified Reference Material BCR-661

Towards Crack Arrest Testing Using Miniature Specimens

Tensile and low-cycle fatigue properties of solution annealed type 316L stainless steel plate and TIG-weld exposed to 5 dpa at low-temperature (42°C)

Analysis of the geometry dependence of fracture toughness at cracking initiation by comparison of circumferentially cracked round bars and SENB tests on Copper

Reconstitution techniques qualification and evaluation to study ageing phenomena of nuclear pressure vessel materials (RESQUE)

SCK·CEN contribution to the IAEA Round Robin exercise on WWER-440 RPV weld material: irradiation, annealing and re-embrittlement

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